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Seznam prepoznane referenčne dokumentacije po področjih Stanje na 1. oktober 2020 Priloga Praktičnih smernic 1.05: Uporaba splošne referenčne dokumentacije v upravnih postopkih Seznam je dodatek k Praktičnim smernicam PS 1.05 in vključuje osnovne zakonodajne predpise, dokumente, standarde in ostalo referenčno dokumentacijo, razvrščeno po področjih jedrske in sevalne varnosti, ki jo je ali pa jo lahko poleg domače zakonodaje pri odločanju o vlogah upravljavca URSJV upošteva kot referenčno dokumentacijo. Načeloma se upoštevajo vedno zadnje veljavne revizije navedenih dokumentov, razen če ni dogovorjeno drugače oziroma v primeru, da zadnja veljavna revizija dokumenta ni uporabna za obstoječi objekt. Seznam referenčne dokumentacije ni popoln in tudi ne pokriva prav vseh področij jedrske in sevalne varnosti. Ker je seznam tudi izredno obsežen, ne moremo stalno zagotavljati, da je prav vsak, v njem naveden dokument, primeren za uporabo v konkretnem upravnem postopku. Seznam je zato zgolj v pomoč pri izbiri ustrezne referenčne dokumentacije v skladu s priporočili Praktičnih smernic 1.05. Seznam periodično obnavljamo oziroma dopolnjujemo glede na nove zahteve zakonodaje, novih standardov in ostale referenčne dokumentacije. [1]

SEZNAM PREPOZNANE REFERENČNE DOKUMENTACIJE ... · Web viewINTERNATIONAL ATOMIC ENERGY AGENCY, Leadership and Management for Safety, IAEA Safety Standards Series No. GSR Part 2, IAEA,

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SEZNAM PREPOZNANE REFERENČNE DOKUMENTACIJE PO PODROČJIH

Seznam prepoznane referenčne dokumentacije po področjih

Stanje na 1. oktober 2020

Priloga Praktičnih smernic 1.05: Uporaba splošne referenčne dokumentacije v upravnih postopkih

Seznam je dodatek k Praktičnim smernicam PS 1.05 in vključuje osnovne zakonodajne predpise, dokumente, standarde in ostalo referenčno dokumentacijo, razvrščeno po področjih jedrske in sevalne varnosti, ki jo je ali pa jo lahko poleg domače zakonodaje pri odločanju o vlogah upravljavca URSJV upošteva kot referenčno dokumentacijo. Načeloma se upoštevajo vedno zadnje veljavne revizije navedenih dokumentov, razen če ni dogovorjeno drugače oziroma v primeru, da zadnja veljavna revizija dokumenta ni uporabna za obstoječi objekt.

Seznam referenčne dokumentacije ni popoln in tudi ne pokriva prav vseh področij jedrske in sevalne varnosti. Ker je seznam tudi izredno obsežen, ne moremo stalno zagotavljati, da je prav vsak, v njem naveden dokument, primeren za uporabo v konkretnem upravnem postopku. Seznam je zato zgolj v pomoč pri izbiri ustrezne referenčne dokumentacije v skladu s priporočili Praktičnih smernic 1.05.

Seznam periodično obnavljamo oziroma dopolnjujemo glede na nove zahteve zakonodaje, novih standardov in ostale referenčne dokumentacije.

KAZALO

1Zakonodaja3

1.1Projekt objekta3

1.2Stanje SSK3

1.3Kvalifikacija opreme4

1.4Staranje objekta4

1.5Varnostne analize5

1.6Uporaba obratovalnih izkušnj ter obratovalni kazalniki objekta5

1.7Sistemi vodenja in organiziranosti upravljalca5

1.8Varnostna kultura6

1.9Obratovanje objekta in pisni postopki6

1.10Človeški faktor7

1.11Načrt zaščite in reševanja ob izrednem dogodku7

1.12Varstvo pred sevanji8

1.13Radiološki vplivi na okolje10

1.14Ravnanje z radioaktivni odpadki in jedrskim gorivom11

1.15Razgradnja11

1.16Občasni varnostni pregled12

1.17Jedrska in sevalna varnost varnost raziskovalnih reaktorjev12

1.18Neširjenje jedrskega orožja in jedrsko varovanje13

1.19Prevoz jedrskih in drugih radioaktivnih snovi14

2Ostala referenčna dokumentacija15

2.1Projekt objekta15

2.2Seizmično projektiranje sistemov, struktur in komponent22

2.3Stanje struktur, sistemov in komponent25

2.4Kvalifikacija opreme29

2.5Staranje objekta32

2.6Varnostne analize34

2.7Uporaba obratovalnih izkušnj ter obratovalni kazalniki objekta46

2.8Sistem vodenja in organiziranosti49

2.9Varnostna kultura54

2.10Obratovanje objekta in pisni postopki56

2.11Človeški faktor59

2.12Načrt zaščite in reševanja ob izrednem dogodku62

2.13Varstvo pred sevanji66

2.14Radiološki vplivi na okolje68

2.15Ravnanje z radioaktivni odpadki in jedrskim gorivom69

2.16Razgradnja jedrskih objektov73

2.17Občasni varnostni pregled74

2.18Jedrska in sevalna varnost raziskovalnih reaktorjev79

2.19Neširjenje jedrskega orožja in jedrsko varovanje81

2.20Prevoz jedrskih in drugih radioaktivnih snovi84

Zakonodaja

Projekt objekta

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

· Definicije stanj jedrskih objektov (PS 1.06)

Stanje SSK

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Zakon o standardizaciji (Ur.l. RS, št. 59/1999)

· Zakon o tehničnih zahtevah za proizvode in ugotavljanje skladnosti (Ur.l. RS, 99/2004)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

· Vsebina in obseg občasnega varnostnega pregleda sevalnega ali jedrskega objekta (PS 1.01)

Kvalifikacija opreme

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Staranje objekta

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Varnostne analize

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Zakon o varstvu pred požarom in podrejeni pravilniki

· Pravilnik o proti eksplozijski zaščiti in podrejeni standardi

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

· Definicije stanj jedrskih objektov (PS 1.06)

Uporaba obratovalnih izkušnj ter obratovalni kazalniki objekta

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Sistemi vodenja in organiziranosti upravljalca

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

· Vzpostavitev, uvedba, izvajanje in stalno izboljševanje celovitega sistema vodenja (PS 1.07)

Varnostna kultura

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti (ZVISJV-1)

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih (JV4)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vzpostavitev, uvedba, izvajanje in stalno izboljševanje celovitega sistema vodenja (PS 1.07)

Obratovanje objekta in pisni postopki

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih (JV4; Uradni list RS, št. 32, 2011)

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

· Definicije stanj jedrskih objektov (PS 1.06)

Človeški faktor

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih

· Direktiva Sveta 2014/87/Euratom z dne 8. julija 2014 o spremembi Direktive 2009/71/Euratom o vzpostavitvi okvira Skupnosti za jedrsko varnost jedrskih objektov

· Direktiva Sveta 2009/71/Euratom z dne 25. junija 2009 o vzpostavitvi okvira Skupnosti za varnost jedrskih objektov

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Načrt zaščite in reševanja ob izrednem dogodku

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih (UV2)

· Državni načrt zaščite in reševanja ob jedrski ali radiološki nesreč

· COUNCIL DIRECTIVE 2013/59/EURATOM of 5 December 2013 laying down basicsafety standards for protection against the dangers arising from exposure to ionising radiation, and repealing Directives 89/618/Euratom, 90/641/Euratom, 96/29/Euratom, 97/43/Euratom and 2003/122/Euratom

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Varstvo pred sevanji

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih (JV4)

· Uredba o sevalnih dejavnostih (UV1)

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih (UV2)

· Uredba o območjih omejene rabe prostora zaradi jedrskega objekta in o pogojih gradnje objektov na teh območjih (UV3)

· Uredba o zmanjšanju izpostavljenosti zaradi naravnih radionuklidov in preteklih dejavnosti ali dogodkov (UV5)

· Uredba o izvajanju uredb Sveta (ES) in uredb Komisije (ES) o radioaktivnem onesnaženju živil in krme

· Uredba o spremembah in dopolnitvah Uredbe o izvajanju uredb Sveta (ES) in uredb Komisije (ES) o radioaktivnem onesnaženju živil in krme

· Pravilnik o ravnanju z radioaktivnimi odpadki in izrabljenim gorivom (JV7)

· Pravilnik o monitoringu radioaktivnosti (JV10)

· Pravilnik o uporabi virov sevanja in sevalni dejavnosti (SV2/JV2)

· Pravilnik o pogojih za uporabo virov ionizirajočih sevanj v zdravstvu (SV3)

· Pravilnik o posebnih zahtevah varstva pred sevanji in načinu ocene doz

· Pravilnik o obveznostih izvajalca sevalne dejavnosti in imetnika vira ionizirajočih sevanj (SV8)

· Pravilnik o ukrepih varstva pred sevanji na nadzorovanih in opazovanih območjih (SV8A)

· Pravilnik o fizičnem varovanju jedrskih objektov, jedrskih in radioaktivnih snovi ter prevozov jedrskih snovi

· Pravilnik o največjih mejah radioaktivne kontaminacije človekovega okolja in o dekontaminaciji (ne uporabljajo se več določbe 1. do 15. člena) (Z9; SFRJ, št. 8/87)

· Zakon o trajnem prenehanju izkoriščanja uranove rude in preprečevanju posledic rudarjenja v Rudniku urana Žirovski vrh

· Zakon o prevozu nevarnega blaga

· Sklep o objavi prilog A in B k Evropskemu sporazumu o mednarodnem cestnem prevozu nevarnega blaga (ADR)

· Resolucija o nacionalnem programu ravnanja z radioaktivnimi odpadki in izrabljenim gorivom za obdobje 2016–2025 (Uradni list RS, št. 31/16)Uredba Sveta (EGS) št. 737/90 z dne 22. marca 1990 o pogojih, ki urejajo uvoz kmetijskih proizvodov, ki izvirajo iz tretjih držav po nesreči v jedrski elektrarni Černobil

· Uredba Sveta (ES) št. 616/2000 z dne 20. marca 2000 o spremembi Uredbe (EGS) št. 737/90 o pogojih, ki urejajo uvoz kmetijskih proizvodov, ki izvirajo iz tretjih držav po nesreči v jedrski elektrarni Černobil

· Uredba Komisije (ES) št. 1609/2000 z dne 24. julija 2000 o določitvi seznama proizvodov, ki so izvzeti iz uporabe Uredbe Sveta (EGS) št. 737/90 o pogojih, ki urejajo uvoz kmetijskih proizvodov, ki izvirajo iz tretjih držav po nesreči v jedrski elektrarni Černobil

· Uredba Komisije (ES) št. 1635/2006 z dne 6. novembra 2006 o določitvi podrobnih pravil za uporabo Uredbe Sveta (EGS) št. 737/90 o pogojih, ki urejajo uvoz kmetijskih proizvodov, ki izvirajo iz tretjih držav po nesreči v jedrski elektrarni Černobil

· Izvedbena uredba Komisije (EU) št. 297/2011 z dne 25. marca 2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukušima

· Izvedbena uredba Komisije (EU) št. 351/2011 z dne z 11. aprila 2011 o spremembi Uredbe (EU) št. 297/2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukušima

· Popravek Izvedbene uredbe Komisije (EU) št. 351/2011 z dne z 11. aprila 2011 o spremembi Uredbe (EU) št. 297/2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukuima

· Izvedbena uredba Komisije (EU) št. 506/2011 z dne 23. maja 2011 o spremembi Uredbe (EU) št. 297/2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukušima

· Izvedbena uredba Komisije (EU) št. 657/2011 z dne 7. julija 2011 o spremembi Uredbe (EU) št. 297/2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukušima

· Izvedbena uredba Komisije (EU) št. 961/2011 z dne 27. septembra 2011 o uvedbi posebnih pogojev za uvoz krme in živil, ki izvirajo iz Japonske ali so od tam poslani, po nesreči v jedrski elektrarni Fukušima ter razveljavitvi Uredbe (EU) št. 297/2011

· Uredba Sveta (EURATOM) št. 3954/87 z dne 22. decembra 1987 o najvišji dovoljeni stopnji radioaktivnega onesnaženja živil in krme po jedrski nesreči ali kateri koli drugi radiološki nevarnosti

· Uredba sveta (EURATOM) št. 2218/89 z dne 18. julija 1989 o spremembi Uredbe (Euratom) št. 3954/87 o maksimalnih dovoljenih ravneh radioaktivne kontaminacije živil in krme po jedrski nesreči ali kakršnikoli drugi radiološki nesreči

· Uredba Komisije (EURATOM) št. 770/90 z dne 29. marca 1990 o določitvi najvišje dovoljene ravni radioaktivne kontaminacije krme po jedrski nesreči ali kakršni koli drugi radiološki nevarnosti

· Uredba Komisije (EURATOM) št. 944/89 z dne 12. aprila 1989 o določitvi maksimalne dovoljene ravni radioaktivne kontaminacije manj pomembnih živil po jedrski nesreči ali kakršni koli drugi radiološki nesreči

· Uredba Sveta (EGS) št. 2219/89 z dne 18. julija 1989 o posebnih pogojih za izvoz živil in krme po jedrski nesreči ali kakršnikoli drugi radiološki nevarnosti

· Council Directive 96/29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionising radiation (https://eur-lex.europa.eu/legal-content/EN/TXT/?uri=CELEX%3A31996L0029)

· Skupna konvencija o varnosti ravnanja z izrabljenim gorivom in varnosti ravnanja z radioaktivnimi odpadki

· Konvencija o jedrski varnosti

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

Radiološki vplivi na okolje

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti (ZVISJV-1)

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Uredba o sevalnih dejavnostih (UV1)

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih (UV2)

· Pravilnik o uporabi virov sevanja in sevalni dejavnosti

· Pravilnik o monitoringu radioaktivnosti (JV10)

· Pravilnik o načinu vodenja evidenc o osebnih dozah zaradi izpostavljenosti ionizirajočim sevanjem (SV4)

· Pravilnik o pogojih in metodologiji za ocenjevanje doz pri varstvu delavcev in prebivalstva pred ionizirajočimi sevanji (SV5)

Praktične smernice:

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Ravnanje z radioaktivni odpadki in jedrskim gorivom

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o ravnanju z radioaktivnimi odpadki in izrabljenim gorivom (JV7)

· Uredba o sevalnih dejavnostih

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih

· Resolucija o nacionalnem programu ravnanja z radioaktivnimi odpadki in izrabljenim jedrskim gorivom za obdobje 2006-2015 (ReNPROJG)

· Zakon o ratifikaciji Pogodbe med Vlado Republike Slovenije in Vlado Republike Hrvaške o ureditvi statusnih in drugih pravnih razmerij, povezanih z vlaganjem v Nuklearno elektrarno Krško, njenim izkoriščanjem in razgradnjo in skupne izjave ob podpisu pogodbe med Vlado Republike Slovenije in Vlado Republike Hrvaške o ureditvi statusnih in drugih pravnih razmerij, povezanih z vlaganjem v Nuklearno elektrarno Krško, njenim izkoriščanjem in razgradnjo (BHRNEK)

· Skupna konvencija o varnosti ravnanja z izrabljenim gorivom in varnosti ravnanja z radioaktivnimi odpadki

Praktične smernice

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Razgradnja

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o ravnanju z radioaktivnimi odpadki in izrabljenim gorivom (JV7)

· Uredba o sevalnih dejavnostih

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih

Praktične smernice

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Vsebina varnostnega poročila za odlagališče nizko in srednje radioaktivnih odpadkov (PS 1.03)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Občasni varnostni pregled

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

Praktične smernice

· Vsebina in obseg občasnega varnostnega pregleda sevalnega ali jedrskega objekta (PS 1.01)

Jedrska in sevalna varnost varnost raziskovalnih reaktorjev

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o zagotavljanju usposobljenosti delavcev v sevalnih in jedrskih objektih (JV4)

· Zakon o zaščiti pred naravnimi in drugimi nesrečami

· Pravilnik o uporabi virov sevanja in sevalni dejavnosti (JV2/SV2)

· Pravilnik o monitoringu radioaktivnosti (JV10)

· Pravilnik o ravnanju z radioaktivnimi odpadki in izrabljenim gorivom (JV7)

· Uredba o sevalnih dejavnostih

· Uredba o mejnih dozah, radioaktivni kontaminaciji in intervencijskih nivojih

Praktične smernice

· Vsebina in obseg občasnega varnostnega pregleda sevalnega ali jedrskega objekta (PS 1.01)

· Vsebina varnostnega poročila sevalnih ali jedrskih objektov (PS 1.04)

· Obravnava sprememb v sevalnem ali jedrskem objektu (PS 1.02)

Neširjenje jedrskega orožja in jedrsko varovanje

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Pravilnik o fizičnem varovanju jedrskih objektov, jedrskih in radioaktivnih snovi ter prevozov jedrskih snovi

· Pravilnik o dejavnikih sevalne in jedrske varnosti (JV5)

· Pravilnik o zagotavljanju varnosti po začetku obratovanja sevalnih ali jedrskih objektov (JV9)

· Pravilnik o uporabi virov sevanja in sevalni dejavnosti (Uradni list RS, št. 27/18) [V. poglavje]

· Zakon o nadzoru izvoza blaga z dvojno rabo (ZNIBDR)

· Uredba o varovanju jedrskih snovi (UV 6)

· Zakon o zasebnem varovanju (ZZasV-1)

· Uredba o obveznem organiziranju službe varovanja

· Kazenski zakonik

· Odredba o določitvi programa osnovnega strokovnega usposabljanja in programa obdobnega strokovnega izpopolnjevanja varnostnega osebja, ki izvaja fizično varovanje jedrskih objektov, jedrskih ali radioaktivnih snovi ter prevozov jedrskih snovi Ur. l. RS, št. (12/2013)

· Pogodba o neširjenju jedrskega orožja

· Sporazum med Kraljevino Belgijo, Kraljevino Dansko, Zvezno republiko Nemčijo, Irsko, Italijansko republiko, Velikim vojvodstvom Luksemburg, Kraljevino Nizozemsko, Evropsko skupnostjo za atomsko energijo in Mednarodno agencijo za atomsko energijo o izvajanju člena III(1) in (4) Pogodbe o neširjenju jedrskega orožja

· Dodatni protokol k Sporazumu med Republiko Avstrijo, Kraljevino Belgijo, Kraljevino Dansko, Republiko Finsko, Zvezno republiko Nemčijo, Helensko republiko, Irsko, Italijansko republiko, Velikim vojvodstvom Luksemburg, Kraljevino Nizozemsko, Portugalsko republiko, Kraljevino Španijo, Kraljevino Švedsko, Evropsko skupnostjo za atomsko energijo in Mednarodno agencijo za atomsko energijo pri izvajanju člena III(1) in (4) Pogodbe o neširjenju jedrskega orožja

· Konvencija o fizičnem varovanju jedrskega materiala in jedrskih objektov (Sprememba Konvencije o fizičnem varovanju jedrskega materiala iz l. 1985, s spremembo, objavljeno v Ur. listu RS-MP, št. 14/09),

· International Convention for the Suppression of Acts of Nuclear Terrorism (Nuclear Terrorism Convention), IAEA, (2005)

· UREDBA KOMISIJE (Euratom) št. 302/2005 z dne 8. februarja 2005 o uporabi določb Euratom o nadzornih ukrepih

· Priporočilo Komisije z dne 15. decembra 2005 o smernicah za uporabo Uredbe (Euratom) št. 302/2005 o uporabi določb Euratom o nadzornih ukrepih (notificirano pod dokumentarno številko C(2005) 5127) (2006/40/Euratom)

· Priporočilo Komisije z dne 11. 2. 2009 o izvajanju sistema knjigovodstva in kontrole jedrskih snovi upravljavcev jedrskih objektov (notificirano pod dokumentarno številko C(2009) 785) (2009/120/Euratom)

· Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, IAEA Services Series 21, (2014)

· Safeguards Implementation Practices Guide on Establishing and Maintaining State Safeguards Infrastructure, IAEA Services Series 31, (2015)

· Safeguards Implementation Practices Guide on Provision of Information to the IAEA, IAEA Services Series No. 33, (2016)

· Guidelines and Format for Preparation and Submission of Declaration Pursuant to Articles 2 & 3 of the Model Protocol Additional to Safeguards Agreements, IAEA Services Series 11, (2004)

· Safeguards Implementation Practices Guide on Facilitating IAEA Verification Activities, IAEA Services Series 30, (2014)

· Uredba o načinu izdaje dovoljenj in potrdil ter vlogi Komisije za nadzor izvoza blaga z dvojno rabo (Uradni list RS, št. 34/10 in 42/12)

· Uredba Sveta (ES) št. 428/2009 z dne 5. maja 2009 o vzpostavitvi režima Skupnosti za nadzor izvoza, prenosa, posredovanja in tranzita blaga z dvojno rabo

· Uredba (EU) št. 1232/2011 Evropskega parlamenta in Sveta z dne 16. novembra 2011 o spremembi Uredbe Sveta (ES) št. 428/2009 o vzpostavitvi režima Skupnosti za nadzor izvoza, prenosa, posredovanja in tranzita blaga z dvojno rabo – nazadnje posodobljena z Delegirana uredba Komisije (EU) št. 2019/2199 z dne 17. oktobra 2019 o spremembi Uredbe Sveta (ES) št. 428/2009 o vzpostavitvi režima Skupnosti za nadzor izvoza, prenosa, posredovanja in tranzita blaga z dvojno rabo

· Sklep Vlade (št. 803-10/99-1 (N) z dne 6. 5. 1999) o mednarodnih kontrolnih režimih Nuclear Suppliers Group in Zangger Committee

· United Nations Security Council Resolution 1540 (2004)

· United Nations Security Council Resolution 1373 (2001)

· Zakon o omejevalnih ukrepih, ki jih Republika Slovenija uvede ali izvaja skladno s pravnimi akti in odločitvami, sprejetimi v okviru mednarodnih organizacij

· Uredba o preverjanju radioaktivnosti pošiljk, ki bi lahko vsebovale vire sevanja neznanega izvora (Ur. l. RS, št. 10/19)

· IAEA INFICIRC/910 (Joint Statement on Strengthening the Security of High Activity Sealed Radioactive Sources), 2017

· IAEA INFICIRC/918 (Joint Statement on Countering Nuclear Smuggling), 2017

Prevoz jedrskih in drugih radioaktivnih snovi

· Zakon o varstvu pred ionizirajočimi sevanji in jedrski varnosti

· Zakon o prevozu nevarnega blaga - ZPNB

· Sklep o objavi prilog A in B k Evropskemu sporazumu o mednarodnem cestnem prevozu nevarnega blaga (ADR)

· Pravilnik o nalogah varnostnega svetovalca za prevoz nevarnega blaga

Ostala referenčna dokumentacija

Projekt objekta

NRC dokumenti

· 10 CFR Part 50 - “Domestic licensing of product and utilization facilities”

· 10 CFR 54 - “Requirements for renewal of operating licenses for nuclear power plants”

· 10 CFR Part 100 - “Reactor site criteria”

· Standard Review Plan, NUREG-0800

· Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients, Generic Letter 2007-01

· Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Generic Letter 2008-01

· Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors, Generic Letter 2004-02

· Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors, Bulletin 2003-01

· Anticipated Transients That Could Develop into More Serious Events, RIS 2005-29

· Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools, Generic Letter 2016-01

NRC Regulatory Guides

· RG 1.1, "Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps"

· RG 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors"

· RG 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors"

· RG 1.6, "Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems"

· RG 1.7, "Control of Combustible Gas Concentrations in Containment"

· RG 1.9, "Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants"

· RG 1.11, "Instrument Lines Penetrating Primary Reactor Containment"

· RG 1.12, "Nuclear Power Plant Instrumentation for Earthquakes"

· RG 1.13, "Spent Fuel Storage Facility Design Basis"

· RG 1.14, "Reactor Coolant Pump Flywheel Integrity"

· RG 1.20, "Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing"

· RG 1.22, "Periodic Testing of Protection System Actuation Functions"

· RG 1.23, "Meteorological monitoring programs for nuclear power plants"

· RG 1.24, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure"

· RG 1.26, "Quality Group Classifications and Standards for Water, Steam and RG Radioactive-Waste-Containing Components of Nuclear Power Plants"

· RG 1.27, "Ultimate Heat Sink for Nuclear Power Plants (for Comment)"

· RG 1.28, "Quality Assurance Program Criteria (Design and Construction)"

· RG 1.29, "Seismic Design Classification"

· RG 1.30, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment"

· RG 1.31, "Control of Ferrite Content in Stainless Steel Weld Metal"

· RG 1.32, "Criteria for Power Systems for Nuclear Power Plants"

· RG 1.34, "Control of Electroslag Weld Properties"

· RG 1.36, "Nonmetallic Thermal Insulation for Austenitic Stainless Steel"

· RG 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants"

· RG 1.38, "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants"

· RG 1.40, "Qualification of Continuous Duty Safety-Related Motors for Nuclear Power Plants"

· RG 1.41, "Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments"

· RG 1.43, "Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components"

· RG 1.44, "Control of the Use of Sensitized Stainless Steel 1"

· RG 1.45, "Guidance on Monitoring and Responding to Reactor Coolant System Leakage"

· RG 1.47, "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems"

· RG 1.48, "Design Limit and Loading Combinations for Seismic Category I Fluid System Components"

· RG 1.50, "Control of Preheat Temperature for Welding of Low-Alloy Steel"

· RG 1.52, "Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants"

· RG 1.53, "Application of the Single-Failure Criterion to Safety Systems"

· RG 1.54, "Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants"

· RG 1.57, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components"

· RG 1.59, "Design Basis Floods for Nuclear Power Plants"

· RG 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants"

· RG 1.61, "Damping Values for Seismic Design of Nuclear Power Plants"

· RG 1.62, "Manual Initiation of Protective Actions"

· RG 1.63, "Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants"

· RG 1.65, "Materials and Inspections for Reactor Vessel Closure Studs"

· RG 1.68.2, "Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants"

· RG 1.68.3, "Preoperational Testing of Instrument and Control Air Systems"

· RG 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)"

· RG 1.73, "Qualification Tests for Safety-Related Actuators in Nuclear Power Plants"

· RG 1.75, "Physical Independence of Electric Systems"

· RG 1.76, "Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants"

· RG 1.77, "Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors"

· RG 1.78, "Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical"

· RG 1.82, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident"

· RG 1.84, "Design, Fabrication, and Materials Code Case Acceptability"

· RG 1.85, "Materials Code Case Acceptability"

· RG 1.89, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants"

· RG 1.91, "Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants"

· RG 1.92, "Combining Modal Responses and Spatial Components in Seismic Response Analysis"

· RG 1.93, "Availability of Electric Power Sources"

· RG 1.97, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants"

· RG 1.99, "Radiation Embrittlement of Reactor Vessel Materials"

· RG 1.100, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

· RG 1.101, "Emergency Planning and Preparedness for Nuclear Power Reactors"

· RG 1.102, "Flood Protection for Nuclear Power Plants"

· RG 1.105, "Setpoints for Safety-Related Instrumentation"

· RG 1.106, "Thermal Overload Protection for Electric Motors on Motor-Operated Valves"

· RG 1.115, "Protection Against Low-Trajectory Turbine Missiles"

· RG 1.117, "Tornado Design Classification"

· RG 1.118, "Periodic Testing of Electric Power and Protection Systems"

· RG 1.120, "Fire Protection Guidelines for Nuclear Power Plants"

· RG 1.122, "Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components"

· RG 1.124, "Service Limits and Loading Combinations for Class 1 Linear-Type Supports"

· RG 1.125, "Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants"

· RG 1.127, "Inspection of Water-Control Structures Associated with Nuclear Power Plants"

· RG 1.128, "Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants"

· RG 1.129, "Maintenance, Testing and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants"

· RG 1.130, "Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports"

· RG 1.133, "Loose-Parts Detection Program for the Primary System of Light-Water-Cooled Reactors"

· RG 1.137, "Fuel-Oil Systems for Standby Diesel Generators"

· RG 1.141, "Containment Isolation Provisions for Fluid Systems"

· RG 1.142, "Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)"

· RG 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants"

· RG 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1"

· RG 1.149, "Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations"

· RG 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations"

· RG 1.151, "Instrument Sensing Lines"

· RG 1.152, "Criteria for Use of Computers in Safety Systems of Nuclear Power Plants«

· RG 1.155, "Station Blackout"

· RG 1.156, "Qualification of Connection Assemblies for Nuclear Power Plants"

· RG 1.158, "Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants"

· RG 1.162, "Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels"

· RG 1.164, "Dedication of Commercial-Grade Items for Use in Nuclear Power Plants"

· RG 1.165, "Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion"

· RG 1.166, "Pre-Earthquake Planning, Shutdown, and Restart of a Nuclear Power Plant Following an Earthquake"

· RG 1.168, "Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"

· RG 1.169, "Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"

· RG 1.170, "Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"

· RG 1.171, "Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"

· RG 1.172, "Software Requirement Specifications for Digital Computer Software and Complex Electronics Used in Safety Systems of Nuclear Power Plants"

· RG 1.173, "Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants"

· RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis"

· RG 1.176, "An Approach for Plant-Specific, Risk-Informed Decision making: Graded Quality Assurance"

· RG 1.180, "Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems"

· RG 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors"

· RG 1.189, "Fire Protection for Nuclear Power Plants"

· RG 1.192, "Operation and Maintenance Code Case Acceptability"

· RG 1.193 , "ASME Code Cases Not Approved for Use 3 10/2010"

· RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants"

· RG 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors"

· RG 1.196, "Control Room Habitability at Light-Water Nuclear Power Reactors"

· RG 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors"

· RG 1.198, "Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites"

· RG 1.199, "Anchoring Components and Structural Supports in Concrete"

· RG 1.201, "Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance"

· RG 1.204, "Guidelines for Lightning Protection of Nuclear Power Plants"

· RG 1.205, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants"

· RG 1.207, "Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors"

· RG 1.208 , "A Performance-Based Approach to Define Site-Specific Earthquake Ground Motion"

· RG 1.209, "Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants"

· RG 1.210, "Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants"

· RG 1.211, "Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants"

· RG 1.212, "Sizing of Large Lead-Acid Storage Batteries"

· RG 1.213, "Qualification of Safety-Related Motor Control Centers for Nuclear Power Plants"

· RG 1.214, "Response Strategies for Potential Aircraft Threats"

· RG 1.216, "Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure"

· RG 1.218, "Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants"

· RG 1.221, "Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants"

· RG 1.226, "Flexible Mitigation Strategies for Beyond-Design-Basis Events"

· RG 1.227, "Wide-Range Spent Fuel Pool Level Instrumentation"

NUREG

· NUREG/CR-5741, “Technical Bases for RG for Soil Liquefaction”

· NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components"

· NUREG-0737, “Clarification of TMI Action Plan Requirements”

· NUREG-1174, "Evaluation of Systems Interactions in Nuclear Power Plants"

· NUREG/CR-0255 (TREE/1279), "CONTEMPT-LT/028 - A Computer Program for Predicting Containment Pressure-Temperature Response to a Loss-of-Coolant Accident"

· NUREG-0611, "Generic Evaluation of Feedwater Transients and Small- Break Loss-of-Coolant Accidents in Westinghouse Designed Operating Plants"

· NUREG-0588, “Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment”

· NUREG-1431, “Standard Technical Specifications – Westinghouse Plants”

· NUREG/CR-2300, “PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants”

· NUREG/CR-5741, “Technical Bases for RG for Soil Liquefaction”

· NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components"

· NUREG-0737, “Clarification of TMI Action Plan Requirements”

· NUREG-1174, "Evaluation of Systems Interactions in Nuclear Power Plants"

· NUREG-0611, "Generic Evaluation of Feedwater Transients and Small- Break Loss-of-Coolant Accidents in Westinghouse Designed Operating Plants"

· NUREG-2163, "Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule, Final Report"

· NUREG-2174, "Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks, Final Report"

· NUREG-2195, "Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes, Final Report"

· NUREG/CR-6303, "Method for Performing Diversity and Defense-in-Depth Analyses of Reactor Protection Systems"

· NUREG/CR-7000, "Essential Elements of an Electric Cable Condition Monitoring Program"

· NUREG/CR-7002, "Criteria for Development of Evacuation Time Estimate Studies"

· NUREG/CR-7004, "Technical Basis for Regulatory Guidance on Design-Basis Hurricane-Borne Missile Speeds for Nuclear Power Plants"

· NUREG/CR-7005, "Technical Basis for Regulatory Guidance on Design-Basis Hurricane Wind Speeds for Nuclear Power Plants"

· NUREG/CR-7042, "A Large Scale Validation of a Methodology for Assessing Software Reliability"

· NUREG/CR-7122, "An Evaluation of Ultrasonic Phased Array Testing for Cast Austenitic Stainless Steel Pressurizer Surge Line Piping Welds"

· NUREG/CR-7131, "Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports"

· NUREG/CR-7172, "Knowledge Base Report on Emergency Core Cooling Sump Performance in Operating Light Water Reactors"

· NUREG/CR-7175, "Susceptibility of Nuclear Stations to External Faults"

· NUREG/CR-7187, "Managing PWSCC in Butt Welds by Mitigation and Inspection"

· NUREG/CR-7188, "Testing to Evaluate Extended Battery Operation in Nuclear Power Plants"

· NUREG/CR-7226, "Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Base Welds Near Dissimilar Metal Weld Interfaces"

· NUREG/CR-7229, "Testing to Evaluate Battery and Battery Charger Short Circuit Current Contributions to a Fault on the DC Distribution System"

· NUREG/CR-7244, "Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions"

IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series No. SSR-2/1, Vienna ( 2012).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants Specific Safety Guide, IAEA Safety Standards Series SSG-56, Vienna (2020).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of Electrical Power Systems for Nuclear Power Plants Specific Safety Guide, IAEA Safety Standards Series SSG-34, Vienna (2016).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide, IAEA Safety Standards Series SSG-52, 2019

· INTERNATIONAL ATOMIC ENERGY AGENCY, Operational Limits and Conditions and Operating Procedures for Nuclear Power Plants Safety Guide, IAEA Safety Standards Series No. NS-G-2.2, , Vienna (2000).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Seismic Design and Qualification for Nuclear Power Plants, Safety Standards Series No. NS-G-1.6, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, External Events Excluding Earthquakes in the Design of Nuclear Power Plants - Safety Guide, Safety Standards Series No. NS-G-1.5, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Protection against Internal Fires and Explosions in Nuclear Power Plants, Safety Standards Series, NS-G-1.7, IAEA, Vienna, (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Protection against Internal Hazards other than Fires and Explosions in the Design of Nuclear Power Plants -Safety Guide, Safety Standards Series No. NS-G-1.11, IAEA, Vienna, (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of the Reactor Containment and Associated Systems for Nuclear Power Plants, 2019 – Specific Safety Guide, SSG-53, IAEA, Vienna 2019

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Classification of Structures, Systems and Components in Nuclear Power Plants – Specific Safety Guide, SSG-30, IAEA, Vienna 2014

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of Instrumentation and Control Systems for Nuclear Power Plants – Specific Safety Guide, SSG-39, IAEA, Vienna 2016

· INTERNATIONAL ATOMIC ENERGY AGENCY, Human Factors Engineering in the Design of Nuclear Power Plants – Specific Safety Guide, SSG-51, IAEA, Vienna 2019

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of Fuel Handling and Storage Systems for Nuclear Power Plants – Specific Safet Guide, NS-G-1.4, IAEA, Vienna 2003

· INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Protection Aspects of Design for Nuclear Power Plants – Specific Safet Guide, NS-G-1.13, IAEA, Vienna 2005

Ostala dokumentacija

· ACI 318-71, Building Code Requirements for Reinforced Concrete, American Concrete Institute, 1971.

· ACI 318-05, Building Code Requirements for Reinforced Concrete, American Concrete Institute, 2005.

· ACI 349-01, Code Requirements for Nuclear Safety-Related Concrete Structures, American Concrete Institute, 2001.

· ACI 349-06, Code Requirements for Nuclear Safety-Related Concrete Structures, American Concrete Institute, 2007.

· ACI 359, Proposed Standard Code for Concrete Reactor Vessels and Containment, American Concrete Institute, (Draft issued in mid-seventies)

· ANSI/ANS-2.8-1992, Determining Design Basis Flooding at Power Reactor Sites

· ASME B&PV Code, Section III

· ASME Section XI, Division 1

· ASME Section III, Division 1(Withdrawn 06/01/2003)

· ASME Section III 35 34

· ANSI/ANS-58.3-1992 “Physical protection for nuclear safety-related system and components”, American Nuclear Society, 1992

· NUCLEAR ENERGY INSTITUTE, “Probabilistic Risk Assessment (PRA) Peer Review Process Guidance”, NEI-00-02, 2000

Seizmično projektiranje sistemov, struktur in komponent

NRC dokumenti

· 10 CFR Part 50 Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants”.

· 10 CFR 50.55a, “Codes and standards”.

· 10 CFR Part 100, “Reactor Site Criteria”.

· 10 CFR Part 100, Appendix A, “Seismic and Geologic Siting Criteria for Nuclear Power Plants”.

· 10 CFR 100.20, “Factors to be Considered When Evaluating Sites”.

· 10 CFR 100.23, “Geologic and Seismic Siting Criteria”.

· 10 CFR Part 20, “Standards for Protection Against Radiation”.

· 10 CFR Part 50, Appendix A, GDC 1, “Quality Standards and Records”.

· 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena”.

· 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases”.

· 10 CFR Part 50, Appendix A, GDC 44, “Cooling Water”.

· 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants”.

· NUREG/CR-5741, “Technical Bases for RG for Soil Liquefaction”.

· NUREG-0800, Standard Review Plan.

NRC Regulatory Guides

· RG 1.12, “Nuclear Power Plant Instrumentation for Earthquakes”

· RG 1.27, “Ultimate Heat Sink for Nuclear Power Plants

· RG 1.28, "Quality Assurance Program Requirements (Design and Construction)"

· RG 1.29, “Seismic Design Classification”

· RG 1.60, “Design Response Spectra for Seismic Design of Nuclear Power Plants”

· RG 1.61, “Damping Values for Seismic Design of Nuclear Power Plants”

· RG 1.92, “Combining Modal Responses and Spatial Components in Seismic Response Analysis”

· RG 1.122, “Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment and Components”

· RG 1.132, “Site Investigations for Foundations of Nuclear Power Plants”

· RG 1.138, “Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants”

· RG 1.166, “Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post-Earthquake Actions”

· RG 1.198, "Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites”

· RG 1.208, “A Performance-Based Approach to Define Site-Specific Earthquake Ground Motion”

· RG 4.7, "General Site Suitability Criteria for Nuclear Power Stations"

· RG 1.69, “Concrete Radiation Shields for Nuclear Power Plants”

· RG 1.107, “Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures”

· RG 1.127, “Inspection of Water-Control Structures Associated with Nuclear Power Plants”

· RG 1.136, “Materials, Construction, and Testing of Concrete Containments”

· RG 1.142, “Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)“

IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Seismic Evaluation of Existing Nuclear Power Plants”, Safety Reports Series No. 28, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Seismic Hazards in Site Evaluation for Nuclear Installations, Safety Standards Series No. SSG-9, IAEA, Vienna (2010).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Evaluation of Seismic Safety for Existing Nuclear Installations, Safety Standards Series No. NS-G-2.13, IAEA, Vienna (2009).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Standards Series, ‘External Human Induced Events in Site Evaluation for Nuclear Power Plants’, Safety Guide No. NS-G-3.1, IAEA, Vienna (2002).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Safety of Nuclear Power Plants: Design”, Safety Standards Series No. SSR-2/1 (Rev. 1), IAEA, Vienna (2016).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Site Evaluation for Nuclear Installations”, Safety Standards Series No. SSR-1, IAEA, Vienna (2019).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Format and Content of the Safety Analysis Report for Nuclear Power Plants - Safety Guide”, Safety Standards Series No. GS-G-4.1, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Seismic Design and Qualification for Nuclear Power Plants - Safety Guide”, Safety Standards Series No. NS-G-1.6, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Design of the Reactor Containment and Associated Systems for Nuclear Power Plants - Specific Safety Guide”, Safety Standards Series No. SSG-53, IAEA, Vienna (2019).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants - Specific Safety Guide”, Safety Standards Series No. SSG-56, IAEA, Vienna (2020).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Safety Assessment for Facilities and Activities”, Safety Standards Series No. GSR Part 4 (Rev. 1), IAEA, Vienna (2016).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Deterministic Safety Analysis for Nuclear Power Plants”, Safety Standards Series No. SSG-2 (Rev.1), IAEA, Vienna (2019).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Assessment of Vulnerabilities of Operating Nuclear Power Plants to Extreme External Events”, TECDOC Series No. 1834, IAEA, Vienna (2017).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Earthquake experience and seismic qualification by indirect methods in Nuclear Installations”, TECDOC Series No. 1333, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Seismic Evaluation of Existing Nuclear Facilities”, TECDOC Series No. 1202, IAEA, Vienna (2001).

Standardi

· ASME Boiler and Pressure Vessel Code, Section III.

· ASME Boiler and Pressure Vessel Code, Section XI.

· ACI 349, “Code Requirements for Nuclear Safety Related Concrete Structures”.

· ANSI/AISC N690-1994, “Specification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities”.

· ACI 318, “Building Code Requirements for Structural Concrete”.

· ASCE 7, “Minimum Design Loads for Buildings and Other Structures”.

· AISC, “Steel Construction Manual”.

· ASCE 4-98, »Seismic Analysis of safety-Related Nuclear Structures and Commentary«.

· ASCE/SEI 43-05, »Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities«.

· ANSI/ANS-2.8-1992, “Determining Design Basis Flooding at Power Reactor Sites”.

· ASCE/SEI 7, “Minimum Design Loads for Buildings and Other Structures”.

· ASME Boiler and Pressure Vessel Code, Section III.

· ANSI/AISC N690-1994, “Specification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities”.

· ACI 318, “Building Code Requirements for Structural Concrete”.

· ACI 349-01, “Code Requirements for Nuclear Safety-Related Concrete Structures”.

· AISC 325-05, “Steel Construction Manual”, Thirteenth Edition.

· American Society for Testing and Materials (ASTM) International, ASTM D 5778, “Standard Test Method for Performing Electronic Friction Cone and Piezocone Penetration Testing of Soils,” 1995.

· American Society for Testing and Materials (ASTM) International, ASTM D 1586, “Standard Test Method for Penetration Test and Split-Barrel Sampling of Soils,” 1999

· American Society for Testing and Materials (ASTM) International, ASTM D 1587, “Standard Practice for Thin-Walled Tube Sampling of Soils for Geotechnical Purposes,” 2000.

· American Society for Testing and Materials (ASTM) International, ASTM D 4220, “Standard Practices for Preserving and Transporting Soil Samples,” 2000.

· American Society for Testing and Materials (ASTM) International, ASTM D 1557, “Standard Test Methods for Laboratory Compaction Characteristics of Soil Using Modified Effort (56,000 feet-lbf/feet3 [2,700 kN-m/m3]),” 2002.

· American Society for Testing and Materials (ASTM) International, ASTM D 4044, “Standard Test Method (Field Procedure) for Instantaneous Change in Head (Slug) Tests for Determining Hydraulic Properties of Aquifers,” 2002.

· American Society for Testing and Materials (ASTM) International, ASTM D 2850, “Standard Test Method for Unconsolidated Undrained Triaxial Compression Test on Cohesive Soils,” 2003.

· American Society for Testing and Materials (ASTM) International, ASTM D 4767, “Standard Test Method for Consolidated Undrained Triaxial Compression Test for Cohesive Soils,” 2004.

· American Society for Testing and Materials (ASTM) International, ASTM D 6913, “Standard Test Method for Particle Size Distribution (Gradation) of Soils Using Sieve Analysis,” 2004.

· American Society for Testing and Materials (ASTM) International, ASTM D 2435, “Standard Test Method for One-Dimensional Consolidation Properties of Soils Using Incremental Loading,” 2004.

· American Society for Testing and Materials (ASTM) International, ASTM D 3080, “Standard Test Method for Direct Shear Test of Soil Under Consolidated Drained Conditions,” 2004.

· American Society for Testing and Materials (ASTM) International, ASTM D 2166, “Standard Test Method for Unconfined Compressive Strength of Cohesive Soils,” 2006.

· American Society of Civil Engineers, ASCE 4-98, “Seismic Analysis of Safety-Related Nuclear Structures and Commentary,” 2000.

· American Society of Civil Engineers (ASCE), Editing Board and Task Groups of the Committee on Nuclear Structures and Materials of the Structural Division, “Structural Analysis and Design of Nuclear Plant Structures,” ASCE 1980.

· ASME/ANS-RA-Sa-2009, “Standard for Level 1/LargeEarly Release Frequency PRA for Nuclear Power Plant Applications«.

Stanje struktur, sistemov in komponent

NRC dokumenti

· US NUCLEAR REGULATORY COMMISSION, 10CFR50.55a, “Codes and standards".

· U.S. NUCLEAR REGULATORY COMMISSION, 10CFR50.59, Appendix B, Appendix J, 10CFR 50.55, 10CFR 50.65.

· U.S. NUCLEAR REGULATORY COMMISSION, 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants",

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1823, »U.S. Plant Experience With Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials«.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1801, “Generic Aging Lessons Learned (GALL) Report, Final Report”.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1431, Vol. 1, »Standard Technical Specifications, Westinghouse Plants«

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1431, Vol. 2, »Standard Technical Specifications, Westinghouse Plants«.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-0933, »A Prioritization of Generic Safety Issues, maintenance and surveillance program«.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-1344, "Erosion/Corrosion-lncluded Pipe Wall Thinning in U. S. Nuclear Power Plants".

· U.S. NUCLEAR REGULATORY COMMISSION Letter, “Revision 1 to the Final Safety Evaluation of EPRI Report, Material Reliability Program Report 1016596 (MRP-227), Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines, (TAC NO. ME0680)«

NRC Regulatory Guides

· RG 1.187, »Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments«

· RG 1.99, »Radiation embrittlement of reactor vessel materials«

· RG 1.121, »Basis for Plugging Degraded Steam Generator Tubes«

· RG 1.160, "Monitoring the Effectiveness of Maintenance Rule at Nuclear Power Plants

IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, Maintenance, Surveillance and Inservice Inspection in NPPs, IAEA Safety Standard Series NS-G-2.6, Vienna (2002).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Conduct of Operation at Nuclear Power Plants, IAEA NS-G-2.14, Vienna (2008).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants, Commissioning and Operation, IAEA SSR-2/2, Vienna (2011).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Modern instrumentation and control for NPP, IAEA, Guidebook, Vienna (1999).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Software for computer based systems important to safety in NPP, IAEA, NS-G-1.1, Vienna (2000).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Instrumentation and control systems important to safety in NPP, IAEA NS-G-1.3, Vienna (2002).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Modifications to Nuclear Power Plants Safety Guide, IAEA Safety Standards Series No. NS-G-2.3, November, Vienna (2001).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Operational Limits and Conditions and Operating Procedures for Nuclear Power Plants Safety Guide, IAEA Safety Standards Series No. NS-G-2.2, Vienna (2000).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants: Operation Safety Requirements, IAEA Safety Standards Series No. NS-R-2, Vienna (2000).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Maintenance Optimization Programme for Nuclear Power Plants, Nuclear Energy Series, No. NP-T-3.8, Vienna (2018).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Risk-informed In-service Inspection of Piping Systems of Nuclear Power Plants: Process, Status, Issues and Development, Nuclear Energy Series, No. NP-T-3.1, Vienna (2010).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Improvement of Effectiveness of In-Service Inspection in Nuclear Power Plants, TECDOC-1853, Vienna (2018).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants, Specific Safety Guide, No. SSG-48, Vienna (2018).

ASME

· ASME Code, Section XI, Rules for In-service Inspection of Nuclear Power Plant Components.

· ASME Code, Section II, Materials.

· ASME Code, Section V, Non-destructive Examination.

· ASME Boiler and Pressure Vessel Code, Section III, Subsection NB.

· ASME Section VIII, Pressure Vessels, Division 1.

· ASME Boiler and Pressure Vessel Code, Case N-597, "Requirements for Analytical Evaluation of Pipe Wall Thinning, Section XI.

· ASME B31.1 Power Piping.

· API 579-1/ASME FFS-1, Fitness-For-Service.

NEI

· NEI-03-08, »Guideline for the Management of Materials Issues«.

· NEI 97-06, “Steam Generator Program Guidelines”.

· NUCLEAR ENERGY INSTITUTE, NUMARC 93-01, “Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”.

INPO

· INPO AP-928, »Work Management Process Description«.

· INPO 05-003, »Performance Objectives and Criteria«.

· INPO AP-913, »Equipment Reliability Process Description«.

· INPO 97-011, »Guidelines for the Use of Operating Experience«.

· INPO 05-004, »Guidelines for the Conduct of Maintenance at Nuclear Power Stations«.

· INPO Good Practice OE 901 Industry Operating Experience Review.

· INPO Good Practice 85-031, Guidelines for the Conduct of Technical Support Activities at NPPs.

EPRI

· »Steam Generator Management Program: Foreign Object Prioritization Strategy for Triangular Pitch Steam Generators«, EPRI, Palo Alto, CA: 2010. 1020989.

· MRP-139, “Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline.”

· MRP-126, "Materials Reliability Program: Generic Guidance for Alloy 600 Management" EPRI, Palo Alto, CA: 2004.1009561.

· MRP-227-A »Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines«. EPRI, Palo Alto, CA: 2011. 1022863.

· MRP-191 »Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR Designs«, EPRI, Palo Alto, CA: 2006. 1013234.

· MRP-228 »Materials Reliability Program: Inspection Standard for Reactor Internals«, EPRI, Palo Alto, CA: 2009. 1016609.

· MRP-227 »Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines«, EPRI, Palo Alto, CA: 2008. 1016596.

· Pressurized Water Reactor Steam Generator Examination Guidelines.", EPRI, Palo Alto, 2007, 1013706.

· Revised Risk-Informed Inservice Inspection Evaluation Procedure, EPRI TR-112657.

· Flow Accelerated Corrosion in Nuclear Power Plants, EPRI TR -106611.

· Recommendations for an Effective Flow-Accelerated Corrosion Program, EPRI NSAC-202L-R4.

· EPRI TR-108936 - Predictive Maintenance Program, Development and Implementation.

· Heat Exchanger Performance Monitoring Guidelines, EPRI NP-7552.Recommendations for an Effective Program to Control the Degradation of Buried Pipe, EPRI TR-1016456

· EPRI, "NDE of Buried Pipes," Report GC-109054.

· EPRI, "NDE Technology for In-Line Inspection of Buried Service Water Piping," report GC-1 08827.

Ostala dokumentacija

· EUROPEAN COMMISSION, ‘NDT Methods of Monitoring Degradation, Proceedings of the Joint EC – IAEA Specialist Meeting held at Petten, The Netherlands on 10 – 12 March 1999’, EUR-18718, EC (1999).

· OECD NUCLEAR ENERGY AGENCY, “Inspection of Digital I&C Systems - Methods and Approaches: Proceedings of a CNRA Workshop”, Garching, Germany 24-26 September 2007, NEA/CNRA/R(2008).

· IEEE Standard 338/87 Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems.

· W. Bamford and J. Hall, “A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends,” Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, ANS, 2003, pp.1071–1081.

· Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449 Revision 4, “Steam Generator Tube Integrity«.

· THE EUROPEAN COMMISSION, “European Safety Practices on the Application of Leak Before Break (LBB) Concept”, Nuclear Regulatory Working Group, Report EUR 18549 EN, (2000).

· ANSI B 31.1 Power Piping.

Kvalifikacija opreme

NRC dokumenti

· U.S. NUCLEAR REGULATORY COMMISSION, 10CFR50, Appendix A, “General Design Criteria for NPP”.

· U.S. NUCLEAR REGULATORY COMMISSION, 10CFR50, Appendix B, “Quality Assurance Criteria for NPP and Fuel Reprocessing Plants”.

· U.S. NUCLEAR REGULATORY COMMISSION, 10CFR50.49, CODE OF FEDERAL REGULATIONS, Environmental Qualification of Electric Equipment for Nuclear Power Plants, Federal Register, Vol. 47, No. 13.

NUREG

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-0800, SRP 3.11, Standard Review Plan (SRP), Environmental Qualification of Mechanical and Electrical Equipment.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-0800, SRP-3.10, , Standard Review Plan (SRP), Seismic and Dynamic Qualification of Mechanical and Electrical Equipment.

· U.S. NUCLEAR REGULATORY COMMISSION, NUREG-0588, Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment.

NRC Regulatory Guides

· RG 1.40, “Qualification of Continuous Duty Safety-Related Motors for Nuclear Power Plants”

· RG 1.63, “Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants”

· RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)”

· RG 1.73, “Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants”

· RG 1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants”

· RG 1.97, ”Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants”

· RG 1.100, “Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants”

· RG 1.158, “Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants”

· RG 1.156, “Qualification of Connection Assemblies for Nuclear Power Plants”

· RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”

· RG 1.180, “Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems”

· RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition) “

· RG 1.209, “Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants”

· RG 1.211, “Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants”

IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, Equipment Qualification in Operational Nuclear Power Plants: Upgrading, Preserving and Reviewing, SRS-3, Safety Reports Series No.3, Vienna (1998).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Seismic Design and Qualification for Nuclear Power Plants, NS-G-1.6, IAEA, Vienna (2003).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment and Verification for Nuclear Power Plants, NS-G-1.2, IAEA, Vienna (2001).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants: Design, SSR-2/1, IAEA, Vienna (2012).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Format and Content of The Safety Analysis Report for Nuclear Power Plants, GS-G/4.1, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants, NS-G-1.9, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Design of Emergency Power Systems for Nuclear Power Plants, NS-G-1.8, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Instrumentation and Control Systems Important to Safety in Nuclear Power Plants, NS-G-1.3, Vienna (2002).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Assessment of Equipment Capability to perform reliably under severe accident conditions, TECDOC 1818, Vienna (2017).

Ostala dokumentacija

· IEEE Std 317-1983, "IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generation Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.63).

· IEEE Std 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.89 and NUREG-0588).

· IEEE Std 323-2003, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers.

· IEEE Std 344-1987, "IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.100).

· IEEE/IEC 60780-323 Nuclear facilities – Electrical equipment important to safety – Qualification, 2016.

· IEEE Std.7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.209).

· IEEE Std 650-2006, “IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations,” Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.210).

· IEEE 383-2003, “IEEE Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations,” Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.211).

· IEEE 649 2006, “IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations.” Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.213)

· IEEE Std 334-1971, "IEEE Trial-Use Guide for Type Tests of Continuous-Duty Class 1 Motors Installed Inside the Containment of Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.40).

· IEEE Std 382-1972, "IEEE Trial-Use Guide for Type Test of Class 1 Electric Valve Operators for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.73).

· IEEE Std 383-1974, "IEEE Standard for Type Test of Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Draft Regulatory Guide 1.131).

· IEEE Std 535-1986, "IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.158).

· IEEE Std 572-1985, "IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations," Institute of Electrical and Electronics Engineers (endorsed by Regulatory Guide 1.156).

· EPRI TR-100516, “Nuclear Power Plant Equipment Qualification Reference Manual”, 1992.

Staranje objekta

NRC dokumenti

· US NUCLEAR REGULATORY COMMISSION, "10CFR50.55a, Codes and standards".

· US NUCLEAR REGULATORY COMMISSION, "10 CFR 50.65, The Maintenance Rule".

· US NUCLEAR REGULATORY COMMISSION, “10 CFR 54, The License Renewal Rule”.

· US NUCLEAR REGULATORY COMMISSION, “10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants“.

· US NUCLEAR REGULATORY COMMISSION, “Standard Review Plan for License Renewal”, NUREG 1800.

· US NUCLEAR REGULATORY COMMISSION, “Generic Aging Lessons Learned (GALL) Report”, NUREG 1801.

· US NUCLEAR REGULATORY COMMISSION, NUREG/CR-6048 ORNL-TM-12371 RV: Pressurized-Water Reactor Internals Aging Degradation Study, Phase I.

· US NUCLEAR REGULATORY COMMISSION, NUREG/CR-6260 INEL-95/0045: Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components.

· US NUCLEAR REGULATORY COMMISSION, NUREG/CR-6583 ANL-97/18: Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels.

· US NUCLEAR REGULATORY COMMISSION, NUREG/CR-4513 ANL-93/22: Estimation of Fracture Toughness of Cast Stainless Steel During Thermal Aging in LWR Systems.

· US NUCLEAR REGULATORY COMMISSION, NUREG/CR-6717 ANL-00/27: Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels.

NRC Regulatory Guides

· RG 1.188, “Standard Format and Content for LRA”.

· RG 1.188, »Standard Format And Content For Applications To Renew Nuclear Power Plant Operating Licenses«, Prepublication, US NRC«.

· RG-1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants”.

· RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”.

· RG 1.99, »Radiation embrittlement of reactor vessel materials«.

· RG 1.211, “Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants”.

IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, Fundamental Safety Principles, SF-1, IAEA, Vienna (2006).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Functions and Processes of the Regulatory Body for Safety, IAEA Safety Standards Series No. GSG-13, IAEA, Vienna (2018).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Format and Content of the Safety Analysis Report for Nuclear Power Plants, GS-G-4.1, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), IAEA, Vienna (2016).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Methodology for the Management of Aging of Nuclear Power Plant Components Important to Safety, Technical Reports Series No. 338, IAEA, Vienna (1992).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants, IAEA Safety Standards Series No. SSG-48, IAEA, Vienna (2018).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “SALTO Guidelines, Guidelines for peer review of long term operation and aging management of nuclear power plants”, IAEA Services Series No.17, IAEA, Vienna (2008).

· INTERNATIONAL ATOMIC ENERGY AGENCY, ‘Assessment and Management of Aging of Major NPP Components Important to Safety: Concrete Containment Buildings’, IAEA-TECDOC-1025, IAEA Vienna (1998).

· INTERNATIONAL ATOMIC ENERGY AGENCY, ‘Assessment and Management of Aging of Major NPP Components Important to Safety: PWR Pressure Vessels’, IAEA-TECDOC-1120, IAEA Vienna (1999).

· INTERNATIONAL ATOMIC ENERGY AGENCY, 'Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: PWR Vessel Internals', IAEA TECDOC No. 1557, IAEA, Vienna (2017).

· INTERNATIONAL ATOMIC ENERGY AGENCY, ‘Management of Aging of I&C Equipment in Nuclear Power Plants’, IAEA-TECDOC-1147, IAEA, Vienna (2000).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Data Collection and Record Keeping for the Management of Nuclear Power Plant Aging, Safety Series No. 50-P-3, IAEA, Vienna (1992).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “The IAEA database on aging of RPV welds and steels”, Working Material, IWG-LMNPP 95/5, IAEA Vienna (1995).

· INTERNATIONAL NUCLEAR SAFETY ADVISORY GROUP, ‘Safe Management of the Operating Lifetimes of Nuclear Power Plants’, INSAG-14, IAEA, Vienna (1999).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Management of Life Cycle and Aging at Nuclear Power Plants: Improved I&C Maintenance”, IAEA TECDOC Series No. 1402, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Ageing Management for Nuclear Power Plants: International Generic Ageing Lessons Learned (IGALL),” Safety Reports Series No. SR-82, IAEA, Vienna (2015).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “ Handbook on Ageing Management for Nuclear Power Plants,” Nuclear Energy Series NP-T-3.24, IAEA, Vienna (2017).

NEI

· NUCLEAR ENERGY INSTITUTE, “Industry Guideline for Implementing the Requirements of 10CFR54 – The License Renewal Rule”, NEI-95-10.

· NUCLEAR ENERGY INSTITUTE, “Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”, NUMARC 93-01, Rev.4f (2018).

EPRI

· EPRI TR-105090, “Guidelines to Implement the License Renewal Technical Requirements of 10CFR54 for Integrated Plant assessments and Time-Limited Aging Analyses.

ASME

· ASME Code, Section XI, Rules for In-service Inspection of Nuclear Power Plant Components.

· ASME Code, Section II, Materials.

· ASME Code, Section V, Non-destructive Examination.

Ostala dokumentacija

· OECD NUCLEAR ENERGY AGENCY, “Technical Aspects of Aging for Long term Operation”, NEA/CSNI/R(2002)26.

· OECD NUCLEAR ENERGY AGENCY, »Irradiation Embrittlement and Optimisation of Annealing» NEA/CSNI/R(94)1.

· Nuclear power Plant Life Management in Some European Countries, EUR20415.

· Gilbert Associates, Inc.: Design Specification – Main Steam System – Piping Design/stress Analysis Specification – ASME Section III Class 2&3, Report number: DSP-G500-044687-000.

· Gilbert Associates, Inc.: Design Specification – Main Feedwater System – Piping Design/stress Analysis Specification – ASME Section III Class 2&3, Report number: DSP-G510-044687-000.

· P. Ferroni, Dept. Of Nuclear Engineering, MIT: LWR Pressure Vessel Embrittlemen and Conditions of Validity of Current Predictive Methodologies.

· THE EUROPEAN COMMISSION, “Preparatory Work for an Indicative Program Related to Aging Issues”, Report prepared for the CEC Working Group for Codes & Standards.

Varnostne analize

Deterministične varnostne analize

2.6.1.1 NRC dokumenti

· US NUCLEAR REGULATORY COMMISSION, Domestic Licensing of Production and Utilization Facilities, Code of Federal Regulations 10, Part 50, US Goverment Printing Office, Washington, DC (1995).

· US NUCLEAR REGULATORY COMMISSION, US NRC Regulations Title 10, Code of Federal Regulations Part 54—Requirements For Renewal Of Operating Licenses For Nuclear Power Plants (2009).

· US NUCLEAR REGULATORY COMMISSION, Domestic Licensing of Production and Utilization Facilities, Code of Federal Regulations 10 CFR Part 100 - Reactor site criteria.

· US NUCLEAR REGULATORY COMMISSION, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors, Generic Letter 2004-02, (2004).

· US NUCLEAR REGULATORY COMMISSION, Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients, Generic Letter 2007-01,(2007).

· US NUCLEAR REGULATORY COMMISSION, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Generic Letter 2008-01, (2008).

· US NUCLEAR REGULATORY COMMISSION, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors, Bulletin 2003-01, (2003).

· US NUCLEAR REGULATORY COMMISSION, Anticipated Transients That Could Develop into More Serious Events, RIS 2005-29, (2005).

· US NUCLEAR REGULATORY COMMISSION, Experience With Implementation of Alternative Source Terms, RIS 2006-04, (2006).

NUREG

· NUREG-0933, »A Prioritization of Generic Safety Issues«.

· NUREG-0800, »Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants«, LWR Edition.

NRC Regulatory Guides

· RG 1.70, »Standard format and content of safety analysis reports for nuclear power plants«.

· RG 1.157, »Best-Estimate Calculations of Emergency Core Cooling System Performance«.

· RG 1.206, »Combined License Applications for Nuclear Power Plants (LWR Edition)«

· RG 1.203, »Transient and Accident Analysis Methods«.

· RG 1.206, »Combined License Applications for Nuclear Power Plants (LWR Edition)«..

· RG 1.97, »Instrumentation for Lightwater-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident«..

· RG 1.4, »Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors«

· RG 1.5, »Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors«.

· RG 1.25, »Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors«.

· RG 1.77, »Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors«.

· RG 1.155, »Station Blackout«.

· RG 1.157, »Best-Estimate Calculations of Emergency Core Cooling System Performance«.

· RG 1.195, »Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors«.

2.6.1.2 IAEA dokumenti

· INTERNATIONAL ATOMIC ENERGY AGENCY, Generic safety issues for nuclear power plants with light water reactors and measures taken for their resolution, IAEA TECDOC-1044, IAEA, Vienna (1998).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants - Safety Guide”, Safety Standards Series No. NS-G-1.9, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Format and Content of the Safety Analysis Report for Nuclear Power Plants - Safety Guide. Safety Standards Series No. GS-G-4.1, IAEA, Vienna (2004).

· INTERNATIONAL ATOMIC ENERGY AGENCY, Accident Analysis for Nuclear Power Plants, Safety Report Series No. 23, IAEA, Vienna (2002).

· INTERNATIONAL ATOMIC ENERGY AGENCY, “Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation” Safety Reports Series No. 52, IAEA, Vienna (2008).